Experimental and Numerical Studies on Performance of Passive Decay Heat Removal by a Water Cooling Panel from a High-Temperature Gas-Cooled Reactor
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概要
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An experiment was carried out to simulate passive decay heat removal from a high-temperature gas-cooled reactor based on water cooling panel system. The experiment is aimed at investigating the temperature distribution of the system and the effectiveness of decay heat removal. The experimental apparatus consists of a pressure vessel of 1 m in diameter and 3 m in height, bristling with nineteen stand pipes atop and containing internal heaters with a maximum heating rate of 100 kW to simulate the decay heat of the core. The pressure vessel is surrounded by the water cooling panels in an air-filled cavity, which resembles the actual reactor installation. The computational code THANPACST2 was benchmarked by the experimental data to verify its numerical methods including a newly-proposed axi-symmetrical model of the three-dimensional structures of the stand pipes by porous body cells. Under the conditions of helium gas pressure of 0.47 MPa and temperatures up to 430°C in the pressure vessel, the temperatures of the critical spots near the top of the pressure vessel, where peak temperatures appeared, were estimated within discrepancies between -25 and +70°C from the experimental data. The heat transferred to the cooling panel was estimated to be 4.1% less than the experimental value.
- 一般社団法人 日本原子力学会の論文
- 1999-05-25
著者
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Takada Shoji
Department Of Advanced Nuclear Heat Technology Oarai Research Establishment Japan Atomic Energy Rese
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Sudo Yukio
Office Of Planning Headquarters Japan Atomic Energy Research Institute
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Inagaki Yoshiyuki
Department Of Advanced Nuclear Heat Technology Oarai Research Establishment Japan Atomic Energy Rese
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Takada Shoji
Department Of Advanced Nuclear Heat Technology Oarai Research Establishment Japan Atomic Energy Rese
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Suzuki Kunihiko
Center For Neutron Science Takai Research Establishment Japan Atomic Energy Research Institute
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